AC600 非能动安全壳冷却系统的概率安全分析  

Probabilistic Safety Analysis of AC600 PassiveContainment Cooling System

作　　者：王建瑜[1] 曾曦[1] 张康[2] 周文娟[2] 陈廷相[2] 杨修周[2] 邰亚传[2] 

机构地区：[1]中国核动力研究设计院 [2]上海交通大学

出　　处：《核动力工程》1998年第2期149-153,161,共6页Nuclear Power Engineering

摘　　要：ＡＣ６００是我国改进型压水堆核电站。本文对其在概念设计阶段的非能动专设安全设施中的安全壳冷却系统进行了概率安全分析（ＰＳＡ）。文中采用故障树技术，定量计算出了系统的不可用度及其置信区间、主要部件故障对不可用度的贡献和各组成单元的重要度等，并将计算结果与国内外现有压水堆核电站进行了比较。经比较得出ＡＣ６００采用非能动安全壳冷却系统，将能明显提高核电站的安全性、可靠性和经济性，由于它是一种新的设计，因此围绕系统的实施，还有许多课题需要深入研究。This paper presents the probabilistic safety analysis(PSA)of containment cooling system in passive special safety facility for Chinese advanced PWRs of nuclear power plants AC600.The unavailability of the system,contribution of main parts fault to the unavailability and the key importance of each component are calculated by fault tree analysis technology.Comparing the results of the several existed PWRs at home and abroad,it can be concluded that passive containment cooling system of AC600 has a considerable improvement in terms of safety,reliability and economics.As a new design,it has a lot of topics to study further.

关 键 词：非能动 安全壳 冷却系统 概率安全分析 故障树 

分 类 号：TL364.3[核科学技术—核技术及应用]